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1 article for “mcnp x”
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Thermal-hydraulic Safety Assessment of a Miniature Neutron Source Reactor
Abstract: The main objective of this study is to assess the thermal-hydraulic safety capability of the PLTEMP/ANL v 4.0 in analyzing Ghana Research Reactor-1 (GHARR-1), with vertical fuel rods cooled by natural convection, operating at a nominal power (30 kW) with sufficient safety margins. The neutronic analysis of the core was performed using MCNP X code, where parameters of interest were the power distributions and the power peaking factors. The thermal-hydraulic …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 3, 2013 · pp. 18–44 Read article